ML20077R945

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Proposed Tech Specs Section 3/4.3.8 Re Removal of Turbine Overspeed Protection
ML20077R945
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 01/11/1995
From:
Public Service Enterprise Group
To:
Shared Package
ML20077R939 List:
References
NUDOCS 9501230205
Download: ML20077R945 (7)
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Text

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4 ATTACHMENT 2 ]

TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES LICENSE AMENDMENT APPLICATION REMOVAL OP' TUR.BINE OVERSP3ED PROTECTION i FROM THE TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NPF-57 i HOPE CREEK GENERATING STATION NLR-N94173 DOCKET NO. 50-354 LCR 94-25  !

The following Technical Specifications for Facility Operating License No. NPF-57 are affected by this License Amendment Request:

Bchnical Specification Paces 3/4.3.8 ix and xviii

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3/4.3.8 3/4 3-103 and 3/4 3-104 B 3/4.3.8 B 3/4 3-7 i

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9501230205 950111 PDR P ADOCK 05000354 PDR

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INDEX LIMITING CONDITIONS FOR OPERATION AND CURVEILLANCE REQUIREMENTS SECTION PAGE Table 3.3.7.4-1 Remote Shutdown Monitoring

  • Instrumentation......................... 3/4 3-75 Table 3.3.7.4-2 Remote Shutdown Systems Controls........ 3/4 3-77 Table 4.3.7.4-1 Remote Shutdown Monitoring Instrumentation Surveillance Requirements............................ 3/4 3-82 Accident Monitoring Instrumentation... ....l.............. 3/4 3-E4 Table 3.3.7.5-1 Accident Monitoring Instrumentation..... 3/4 3-85 Table 4.3.7.5-1 Accident Monitoring Instrumentation Surveillance Requirements....... ....... 3/4 3-87 Source Range Monitors.................. .................. 3/4 3-88 Traversing In-Core Probe System. ......................... 3/4 3-89 Loose-Part Detection System............................... 3/4 3-90 Radioactive Liquid Ef fluent Monitoring Instrumentation.... 3/4 3-91 Table 3.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation.............. 3/4 3-92 Table 4.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements............................ 3/4 3-94 Radioactive Gaseous Effluent Monitoring Instrumentation... 3/4 3-96 Table 3.3.7.10-1 Radioactive Gaseous Effluent Refl ut ud4 Monitoring Instrumentation............. 3/4 3-97

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Table 4.3.7.10-1~ Radioactive Gaseous Effluent Monitoring

  • Instrumentation Surveillance Requirements........................... 3/4 3-100 3/473.8 TURBINEOVERSPEEDPROTECTIONSYSh...................... 3/4 3-103 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTU/. TION INSTRUMENTATION........................................... 3/4 3-105 Table 3.3.9-1 Feedwater/ Main Turbine Trip System Actuation Instrumentation................. 3/4 3-106
HOFE CREEK ix

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BASES SEC'!ON '

PAGE INSTRUMENTATION (Continued) '

Seismic Monitoring Instrumentation... .............. B 3<4 3-4 Meteorological Monitoring Instrumentation... ........ B 3/4 3-4 ,

Remote Shutdown Monitoring Instrumentation and Controls........ ............................ B 3/4 3-5  :

Accident Monitoring Instrumentation......... .. . B 3/4 3-5 Source Range Monitors.... .... ............... ..... B 3/4 3-5 Traversing In-Core Probe System. .................... B 3/4 3-5 Loose-Part Detection System....... .... . 7 ' ', .. B 3/4 3-6

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Ne/ 4c8 Radioactive Liouid Effluent Monitoring pM4 Instrumentation..... .. ............. B 3/4 3-6 losM I Radioactive Gaseous Effluent Monitoring Instrumentation.............. ............. .... . B 3/4 3-6 [

d74.3.8 TURBINE OVERSPEED PROTECTION SYSTE.M)...... . ....... B 3/4 3-7  !

3/4.3.9 FEE 0 WATER /Mi!N TURBINE TRIP SYSTEM ACTUAT.*0N INSTRUMENiATION... ........................ .. .. B 3/4 3-7 Figure B1/4 3-1 Reactor vessel Water Level. .. B 3/4 3 8 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM... ..... .. ... .. B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES. . . . . . . . .. . . B 3/4 4-la 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.. . . . . ......... ..... B 3/4 4-3 Operational Leakage.................................. B 3/4 4-3 3/4.4.4 CHEMISTRY............... .. ....... ........ ...... B 3/4 4-3 3/4.4.5 SPECIFIC ACTIVITY....... ... ................ ...... B 3/4 4-4 3/4.4.6 PRESSURE / TEMPERATURE LIMITS... . ...... ... .. ..... B 3/4 4 5 Table 83/4.4.6-1 Reactor Vessel Toughness. .. .. .. B 3/4 4-7 Figure 83/4.4.6-1 Fast Neutron Fluence

~ (E>1Mov) at (1/4)T as a Function of Service Life... ... . B 3/4 4-B HOPE CREEK xviii Amendment No. 3  !

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, INSTRUMENTATION

[3/4.3.8/URBINEOVER D PROTECTIO STEM

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L TING CONDIT N FOR OPERATI -

1 1 1 1 1 3.3.8 At ast one turbi overspeed prot tion system s 1 be_ OPERABLE.

APPLIC ILITY: OPER ONAL CONDITIONS and 2.

ACTk: .

a. With ne turbine cont valve, or o main stop valve r high pressur a  ;

tu ine steam lead operaole and/ with one combin intermediate

. Ive per low pre ure turbine s am lead inoperab , restore tne inoperable valv s) to OPERAB status within 72 tours or close c*

least one va e in the affe ed steam lead (s) isolate the t ine from the s am supply wit n the next 6 hou .  ;

b. With t above requir turbine overspe protection sys otherwise {

inop able, within hours isolate.t turbine,from t steam supply. , .

SURVEIL CE REQUIREM S 1 1 1 1 1

4. 8.1 The pro sions of Specifi tion 4.0.4 are applicable. ,

4.3.8.2 Th bove required tu ine overspeed p tection syste shall be ,

demonstra d OPERABLE: ,

. At least once er 7 days by: l

1. Cyc g each of the f lowing valves chrough at le one. I c late cycle fro he running p tion:

a) For the o rspeed protec on control sy' es; l) x low pressur combined int diate valv -

b) r the electri 1 overspeed t p system an he mechani al overspeed tri system;

1) Fou igh pressure in stop val s, and i
2) ix low pressu combined i reediate v ves.

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<.i HOPE CREEK 3/4 3-103 Amendment No.19 ,

V g c -a m e _.6 __ .~.,,,my_ 9--- --7-- 9

hSTRUMENTATIOV SURVEILLINCEREQUIRE ,

TS (Continu ) , ,

b. At once p 31 days by: -
1. Cycli each of the fo)1 - ing valves the ogh at least one c ete cycle from e running posit n:

) Fe- the ov specd protectio control system;

1) F r high pressu turbine control ves b) F the electrica overspeed trip em and the chanica' ove ed trip system-
1) Four h pressure tu e control valve
c. t least once p 18 months by p orinance of a C EL CALIBRATIO of the turbi overspeed prote ion instrumenta n.

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d. At less nee per 40 mont by disassembli at least one each of the a ve valves and p orming a visualj nd surface ins ction of al alve seats, dis and stems and efifying no una eptable flaws excessive corr on. If unaccep ble flaws or essive corro on j are found, all er valves of t type shall b nspected. /

gqlace b liN "#

HOPE CRICK 3/4 3-104 - - --

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INSTRUMENTATION  ;

BASES

/4.St8 TURBINEJhERSPEEDPRIECTIONSYSJfM This spe fication i provided t ensure that e turbine ov speed rotection stem instr entation a the turbine peed control alves are OPERABLE a d will prot t the turb'ne from exce ive overspee . Protecti from tur ne excessi overspeed s required nce excessiv overspeed andthe

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turbin could gener te potenti ly damaging issiles whic could impa

, (_dama safety rel ed compone ts, equipmen or structure i 3/4.3.9 FEE 0 WATER / MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATIO_N_ i The feedwater/ main turbine trip system actuation instrumentation is pro-vided to initiate action of the feedwater system / main turbine. trip system in the event of a high reactor vessel water level (Level 8) to mitigate potential l damage to the main turbine. l

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  • INSERT 1 3/4.3.8 DELETED INSERT 2 THIS PAGE IhTENTIONALLY BLANK l

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